Overview of R&amp;D on Plasma-Facing Materials and Components in China

Luo, Guang–Nan; Li, Q.; Chen, J. M.; Liu, X.; Liu, W.; Zhou, Zhangjian; Yao, Damao

doi:10.13182/fst12-a14104

Cited by 35 publications

(10 citation statements)

References 12 publications

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“…EAST is a fully superconducting tokamak aimed at longpulse high-performance discharge [17]. The upper divertor of EAST was updated to an active-cooling tungsten divertor in 2014 [18]. A series of feedback-controlled radiative divertor experiments [19] are carried out to explore the operation window for both high-performance plasma and low divertor heat load.…”

Section: Introductionmentioning

confidence: 99%

Investigation of the double peak in the visible-light range of radiative divertor emission profiles on the EAST tokamak

Guo¹,

Lu²,

Jia³

et al. 2021

Plasma Phys. Control. Fusion

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The double-peaked emission profile has been identified by tomographic reconstruction from the signals of the tangentially viewing visible-light imaging system on EAST. In the upper-single-null discharge with neon seeding, two light emission peaks are located near the X-point and in the high-field-side (HFS) scrape-off layer (SOL) on the poloidal cross-section while the outer divertor target is still attached. The double-peaked emission phenomenon has not been reported for other tokamaks. In particular, the existence of the emission peak near the X-point under the attached condition is unexpected because it is usually an indication of X-point multifaceted asymmetric radiation from the edge under the detached condition. Therefore, it is of fundamental importance for the divertor physics to make clear the mechanism of the double-peaked emission phenomenon. The computational simulations with SOLPS-ITER and DIVIMP are performed in this work. The simulated results show the contribution of W impurity to the double-peaked emission profile is negligible with the upper tungsten divertor. Considering the existence of a lower carbon divertor in EAST, the influence of the possible deposition of the carbon on the upper divertor is further investigated. The simulating CIII (465 nm) and CII (514 nm) emissions, which make a significant contribution to the visible-light emission in channel B (blue) and G (green), respectively, are found to be similar tothe experimental results. The emission peak near the X-point is related to the carbon deposited on the dome, while that in the HFS SOL is contributed by the carbon on the inner baffle. The ionization source of the carbon impurity and the net force pointing to the X-point are analyzed to understand the concentration of the carbon impurity near the X-point, which in turn causes the emission peak.

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Section: Introductionmentioning

confidence: 99%

Investigation of the double peak in the visible-light range of radiative divertor emission profiles on the EAST tokamak

Guo¹,

Lu²,

Jia³

et al. 2021

Plasma Phys. Control. Fusion

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“…where F is the poloidal current flux function, R and Z are radial and axial co-ordinates in a cylindrical coordinate system respectively, and P is the pressure [5] . In actuality, calculating the above equation is usually taken in the following form [6] :…”

Section: Introductionmentioning

confidence: 99%

Equilibrium Reconstruction and Its Integration in J-TEXT

Zhang

Sun

et al. 2016

Plasma Sci. Technol.

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The equilibrium fitting code (EFIT) and its application in the J-TEXT tokamak are integrated by the Matlab language. The function of analysis and visualization to the results is added. In addition, the experiment data measured by soft X-ray (SXR) are used to calculate plasma equilibrium as a constraint condition. The improved EFIT code is used for J-TEXT discharge and the profiles of plasma parameters such as flux function, safety factor q, pressure and current density are obtained from the reconstructed configurations.

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“…The facility's major radius is 1.05 m, minor radius is 0.27 m. Apart from the usual external diagnostic equipment, such as magnetic probes, Rogowski coils and so on, J-TEXT also has internal diagnostic equipment, mainly including the high resolution laser polarimeter interferometer system (POLARIS), the soft X-ray imaging diagnostic system (SXR) and the electron cyclotron emission radiometer (ECE). These diagnostic data can all serve as an internal constraint to yield a best fit of plasma equilibrium [6,7] .…”

Section: Introductionmentioning

confidence: 99%

Equilibrium Reconstruction and Integration of EFIT with Diagnoses in J-TEXT Tokamak

Hailong¹,

Xu²,

Zhang³

2016

Plasma Sci. Technol.

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The EFIT program is integrated with the high resolution laser polarimeter interferometer system (POLARIS), the soft X-ray imaging diagnostic system (SXR) and the electron cyclotron emission radiometer (ECE) in the J-TEXT tokamak. Then some internal information about Faraday angle and the position of safety factor q=1 can be obtained as a constraint to EFIT. The modified EFIT code is used to calculate the internal parameters such as flux function, safety factor q, pressure and current density.

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Overview of R&D on Plasma-Facing Materials and Components in China

Cited by 35 publications

References 12 publications

Investigation of the double peak in the visible-light range of radiative divertor emission profiles on the EAST tokamak

Investigation of the double peak in the visible-light range of radiative divertor emission profiles on the EAST tokamak

Equilibrium Reconstruction and Its Integration in J-TEXT

Equilibrium Reconstruction and Integration of EFIT with Diagnoses in J-TEXT Tokamak

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